ML112030734

Millstone Unit 3 - Draft - Outlines (Folder 2)

ML112030734
Person / Time
Site:	Millstone
Issue date:	06/27/2011
From:	NRC Region 1
To:
JACKSON D E RGN-I/DRS/OB/610-337-5306
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ML110030662	List: IR 05000423/2011302 ML111860296 ML112030663 ML112030719 ML112030734 ML112030746 ML112030794 ML112030812 ML112030862 ML112031001 ML112490411
References
TAC U01832
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Text

ES-401 PWR Examination Outline Form ES401-2 Facility:

Millstone 3 Date of Exam: July 18 th , 2011 RO K/A Category SRO-Only Points Group K A A G A2 G* Total KIilllIA A 1 2 1 2 3 4

• Total l. Emergency

& 1 , 1 2 4 3 3 18 3 3 6 Abnormal Plant Evolutions 2 1 1 N/A 2 2 N/A 2 9 2 2 4 Tier Totals 6 2 3 6 -) 5 27 5 5 10 2. 1 5 2 1 5 0 1 4 -) 2 3 3 28 3 2 5Plant Systems 2 0 0 2 2 3 1 0 1 0 0 1 10 2 1 3 Tier 5 2 7 3 2 4 3 2 3 4 38 5 3 8 Totals 3. Generic Knowledge and 1 2 3 4 1 2 4 3 Abilities Categories 7 4 2 2 1 2 l2T-2 Note: Ensure that at least two topics from every applicable KJ A category are sampled within each tier ofthe RO and SRO-only outlines (i. c., cxcept for onc category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KJ A category shan not be lcss than two). Thc point total for eaeh group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D ofES-40l for guidance regarding the elimination of inappropriate KJ A statements. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting as second topic for any system or evolution. Absent a plant-specific priority, only those KJAs having an importance rating (IR) of2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively. Select SRO topics for Tiers 1 and 2 from the shaded systems and KJ A categories.

7.

• The generic (G) KJAs in Tiers 1 and 2 shan be selected from Section 2 ofthe KJA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l.b of ES-401 for the applicable KJAs. On the following pages, enter the KJ A numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category.

Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. For Tier 3, select topics from Section 2 of the KJ A catalog, and enter the KJ A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO to KJAs that are linked to lOCFR55.43.

ES-401 2 Form ES-401-2

• ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

-TIer IIGroup 1 (RO) 000007 Reactor Trip Stabilization

-Recovery 1000008 Pressurizer Space Accident 1reak LOCA 1 3 000011 Large Break LOCA 1 3 000015/17 RCP Malfunctions 14 000022 Loss of Reactor Coolant Makeup / 2 000025 Loss ofRHR System / 4 000026 Loss of Component Cooling Water /8 29 ATWS /1 am Gen. Tube 000054 Loss ofackout 16 000057 Loss of Vital AC Elec. Inst. Bus /6 000058 Loss of DC Power 16 000062 Loss of Service Water Instrument Ai< fSecondary

• 000077 Generator Voltage and Electric Grid Disturbances I 6 KIA Category Totals: K G 1 2 1 2 1 1 1 5 I 3 2 1 6 4 : 1 2 2.4.49 2.4.35 2.2.37 2 1 KIA Topic(,) IR # Knowledge ofthe reasons for the actions in 4.0/4.6 1 :theEOP Ability to operate and/or monitor control of 3.6/3.6 2 Pzr level Ability to operate/monitor CVCS 3.7/3.5 3 Knowledge of the interrelations between pumps and a large break LOCA Ability to determine/interpret the cause of 3.0/3.5 5 RCP failure Ability to determine/interpret Charging Pump 3.2/3.7 6 problems Knowledge ofthe operational implications of 3.9/4.3 7 a loss ofRHRS during all modes of operation Ability to perform actions without reference 4.6/4.4 8 to procedures requiring immediate operation of system components and controls Knowledge oflocal auxiliary operator tasks 3.8/4.0 9 and the resultant operational effects Ability to determine operability and/or 3.6/4.6 10 availability of safety related equipment Knowledge ofthe operational implications of 3.6/4.2 the effects of feed introduction on a dry SG Knowledge of the reasons for the actions 4.3/4.6 contained in the EOP Ability to operate and/or monitor manual 3.7/3.7 13 inverter swapping Knowledge of the operational implications of 2.8/3.1 14 t=quipmentlin,trumen"tion 3 mine/interpret valve lineup to 2.6/2.9 15 .. h portion of system bypassed .:: 1 Ability to operate and/or monitor remote 2.7/2.5 16 manual loaders Knowledge of ops implication of components, 3.8/4.1 17 capacity, function of emergency systems Knowledge of the operational implications of 3.3/3.5 18 definition of volts, watts, amps, V ARs, power factor 2 4 3 3 Group Point Total:

ES-401 2 Fonn ES-401-2 ES-401 PWR Examination Outline Form Emergency and Abnormal Plant Evolutions

-Tier l/Group 1 E/APE # I Name / Safety K K K A A G KtA Topic(s) IR Function 1 2 3 I 000015117 RCP Malfunctions 7" Ability to determinelinterpret calculation of 2.9 /4 , ....... flow in loop with stopped 000022 Loss of Reactor ... 2.4.6 Knowledge ofEOP mitigation strategies 4.7 ....Coolant Makeup / 000038 Steam Gen. Tube 7 Ability to determinelinterpret plant conditions

4.8 Rupture

13 trom survey of control room 000058 Loss of DC Power 15 .... 2.4.8 Knowledge of how AOPs are used in 4.5 , conjunction with EOPs W/E11 Loss of Emergency I, Ability to determine/interpret facility 4.2 , Coolant Recire. I conditions and selection of W 1E0S Inadequate Heat ...... 2.4.47 Ability to diagnose and recognize trends 4.2 .....Transfer-Loss of Secondary utilizing appropriate control room Heat Sink 14 !i X KIA Category Totals: 0 10 0 0 3 3 Group Point Total:

• • • • • ES-401 3 Fonn ES-401 PWR Examination Outline Fonn Emergency and Abnonnal Plant Evolutions

-Tier l/Group 2 .' E/APE # / Name / Safety K K K A A G KIA Topic(s) IR # Function 1 2 3 1 2 ....000005 Inoperable/Stuck 2 I ...... Knowledge of operational implication of 3.113.9 19 Control Rod / 1 flux tilt .. .'000024 Emergency 4 Knowledge of the interrelations between 2.612.5 20 Boration /1 :. emergency boration and pumps .. 000033 Loss of I' 2A20 Knowledge of operational implications of 3.8/4.3 21 Intennediate Range NI I 7 i

• EOP warnings, cautions, and notes ....2 3.113.5 22 Ability to operate andlor monitor ARM . Accident / 8 .... system I*. 000036 Fuel Handling W IE 14 Loss of CTMT 2 *** Ability to determine/interpret adherence to 3.3/3.8 23 Integrity I 5 . '., appropriate procedures W IE 13 Steam Generator 3 > ***** Knowledge ofthe reasons for manipulation 3.2/3.4 24 Over-pressure 1 4 ....... ...........

of controls to obtain desired results W IE 16 High Containment 2.4.31 Knowledge of annunciators, indications, or 4.2/4.1 25 Radiation I 9 ..' ... response procedures W IE03 Post LOCA 3 .... '.' Ability to operate andlor monitor for desired 3.7/4.1 26 Cooldown Depress. 14 .... operating results W/E08 RCS Overcooling 1 Ability to determine/interpret selection of 3.4/4.2 27 ..PTS!4 .... appropriate procedures KIA Category Point Totals: I ! I 1 2 2 2 Group Point Total: 9

-2 ES-401 PWR Examination Outline Fonn ES-401-2 Emergency and Abnonnal Plant Evolutions

-Tier I1Group 2 (SRO) E/APE#/Name/Safety K K AA. (J KIA Topic(s) IR # Function 2 3 1 .***.. ;. .... 000076 High Reactor Coolant 2 ... Ability to determine/interpret 3.4 82 Activity /9 1< < corrective actions for high fission I. ..... product activity W /E 13 Steam Generator Over--2;2:40 Ability to apply Technical 4.7 83 pressure /4 Specifications for a system Site Specific Instrument Failure ..*... 2:1.23 4.4 84 Ability to perfonn specific system Response AOP 3571 / 7 and integrated plant procedures during all modes of operation Site Specific Loss of All AC X Site 85 Ability to determine/interpret Recovery with the SBO Diesel *** selection/adherence to appropriate ECA-0.3/6

....... procedure

.....* < .. KIA Category Point Totals: 2 12. Group Point Total: 4 ES-401 4 Form ES-401-2 ES-40l PWR Examination Outline Fonn ES-4OJ-2 System # / Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 007 Pressurizer Relief/Quench Tank 008 Component I Cooling Water , 008 Component j Cooling Water I 010 Pressurizer

• Pressure Control II

• 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 026 Containment Spray 026 Containment Spray 039 Main and Reheat Steam Plant Systems -Tier 2/Group 1 fRO) .... K K K K K K A A A A in. I 2 3 4 5 6 1 2 3 4 i ..... 10 ** I' .',,<<. 7 '. ....... .........

.... 3 . * ..<".< i.<. 2.4049 I 1 ....... . I* ***** .'. I .... . 8 ... . 8 8 2.4.4 1 3 1 ..... 6 7 KIA Topic(s) Predict and/or monitor changes in RCP Standpipe level associated with 0 ontrols Predict impact/mitigate isolation of letdown/makeup Knowledge of power supplies to RCS pressure boundary MOVs Ability to perfonn without reference immediate actions Physical connections/cause-effect between PRT and CTMT System Design feature and/or interlock that provides for PRT cooling Predict impact/mitigate the shutting ofthc letdown cooler isolation valves Ability to monitor automatic operation due to SIS Physical connections/cause-effect between PZR PCS and PZR LCS Ability to recognize entry conditions for EOPs/AOPs Knowledge of the effect ofa loss or malfunction of detectors on ESFAS Predict and/or monitor changes in Containment humidity due to operating controls Knowledge of the effect ofa loss or malfunction of CSS on the Ctmt Cooling System Predict and/or monitor changes in Ctmt Spray Pump cooling associated with operating controls lity to manually operate and/or nitor steam dump valves IR 2.512.7 3.4/3.7 2.712.8 4.6/4.4 2.9/3.1 2.6/2.9 2.5/2.7 3.6/3.7 3.2/3.5 4.5/4.7 2.7/3.1 3.1/3.4 3.9/4.1 2.7/3.0 2.8/2.9 # 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Fonn ES-401-2 System # / Name 059 Main Feedwater 061 Auxiliary/

Emergency Feedwater 062AC Electrical Distribution 062AC Electrical Distribution 063 DC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water 076 Service Water 078 Instrument Air 103 Containment KIA Category Point Totals: Plant Systems K K K K K K A 1 2 3 4 5 6 1 4 8 3 2 1 1 8 6 I I 5 2 115 1 0 I 4 Tier 2/Group I (RO) Continued A A A KIA Topic(s) 2 3 4 ",'c,' "". ",' ,. Physical effect between MFW and Steam .. Generator Water Level Control Knowledge of design features or interlocks which provide for "" ", """ , AFW recirculation 5 Ability to monitor automatic

... ', .. ,' operation, including safety-related indicators and controls i '. 2.4.11 Knowledge of abnonnal ,. condition procedures . . '..' Physical

.' effect between DC System and battery charger and battery Knowledge of design features or interlocks which provide for breaker interlocks and cross-ties Physical effect between EDG and AC 10 ...... Ability to manually operate andlor monitor need forlconsequences of manual load shedding on safeguards bus Predict andlor monitor changes in radiation levels associated with operating controls ,., Knowledge of power supplies.' "'" for ESF-actuated MOVs '. Knowledge of design features or interlocks which provide for , Service Water train separation

'.,. Knowledge of design features or interlocks which provide for ',' manual/auto transfer of control 3 Ability to manually operate andlor monitor ESF slave relays "'.'" 2 2 3 3 Group Point Total: IR 3.4/3.4 2.7/2.9 3.5/3.6 4.0/4.2 2.9/3.5 2.9/3.2 4.1/4.4 3.3/3.4 3.2/3.5 3.113.3 2.8/3.2 2.7/2.9 2.7/2.7 # 43 44 45 46 47 48 49 50 51 52 53 54 55 28 4 Form ES-401-2 ES-401 PWR Examination Outline Fonn ES-401-2 Plant S "stems -Tier 2/Group I SRO) ;.;!,; I System # I Name K K K K K K A A A A KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 .. ) 004 Chemical and Volume 28 Predict impact/mitigate 4.3 86 Control 005 Residual Heat Removal ; .;". '.;. 3 .;. ;.; '. ..;............ , depressurizing RCS while hot Predict impact/mitigate 3.1 87 '. ;.. ,;;. RHRPump malfunction 013 Engineered Safety Features Actuation . ;.... 2;2.39 >i Knowledge ofless than or equal to one hour 4.5 88 Tech Spec action " statements for systems 059 Main Feedwater 2.4:4 Ability to recognize 4.7 89 I I*****. entry conditions for < I EOPs/AOPs 078 Instrument Air 1 I; Predict impact/mitigate air dryer and filter 2.9 90 ;;' ; ... malfunctions , KIA Category Point Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 .;./.!

• • • • • • • ES-401 ES-401 PWR Examination Outline Form ES-401-2 System # I Name 011 Pressurizer Level Control 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 027 Containment Iodine Removal 029 Containment Purge 035 Steam Generator 072 Area Radiation Monitoring 079 Station Air 086 Fire Protection Site Specific AMSAC KJ A Category Point Totals: Plant S stems -Tier 2/Group 2 (RO) K K K K K K A I [5 A Ai A ******* 1 2 3 4 5 6 I 2 3 ,4 4 1,<. > ".,.,' '... ' 2.*2044 I I> .,< . c **'i' .6 .. ......'.........*...

1 .. ; '. 3 ., ...*...*....

...... 1 I .' 1 ..... I ! , .'. 1 .. I .........3 I*', . ' .. I x ..... I 0 10 2 2 3 I 0 1 0 0 1 '.. >I KJA Topic(s) Knowledge of the effect on PLC of a loss or malfunction of pressurizer level controllers Ability to interpret control room indications and understand how operator actions affect system and plant Knowledge ofthe effect of a loss or malfunction ofNNI will have on AFW Knowledge of operational implications of the purpose of charcoal filters Knowledge of design features or interlocks which provide for automatic purge isolation Knowledge of the effect ofa loss or malfunction ofSGS on the RCS Knowledge of operational implications of radiation theory, including sources, type, effects Predict impact/mitigate cross-connection with lAS Knowledge of the operational implications of water spray on electrical components Knowledge of AMSAC design features or interlocks Group Point Total: IR 3.113.1 4.2/4.4 3.5/3.7 3.113.4 3.2/3.5 . 4.4/4.6 2.7/3.0 2.9/3.2 3.1/3.4 Site # 56 57 58 59 60 61 62 i 63 64 65 10 ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems Tier 2/Group 2 (SRO) .... " .' System # / Name 017 In-core Temperature Monitor K 1 K 2 K 3 K 4 K 5 K 6 A 1 '8, 2 1:. A 3 A 4 KIA Topic(s) ,,> + Predict impact/mitigate thermocouple open/short IR 3.5 # 91 circuits 035 Steam Generator 1 ******L/........ " Predict impact/mitigate impact 4.6 92 './ on SGS of faulted or ruptured SGs Site Specific AMSAC ******* ...... 2.4.47 "';:;.-" h Ability to diagnose and recognize trends utilizing 4.2 93 ** ...... '., appropriate control room reference material .' i . KIA Category Point Totals: 0 0 0 0 0 0 0 2 0 0 *******1 ..... ,....." Group Point Total: 3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Fonn ES-401-3 Facility:

Millstone Unit 3 Date of Exam: Category KiA # Topic RO SRO-Only l. Conduct of 2.1.8 2.1.31 . 2.1.20 Ability to coordinate personnel activities outside the control room Ability to locate control room switches, controls, and indications, and to determine they "Vll"""] reflect the: desired plant lineup Ability to interpret and execute procedure steps 1R 3.4/4.1 4.6/4.3 # 66 67 1R 4.6 # 94 Operations 2.1.41 Knowledge of the 3.7 95 2. Equipment Control Subtotal 2.2.6 2.2.l4 2.2.38 2.2.39 Knowledge of the process for making changes to procedures Knowledge of the process for controlling equipment configuration or status Knowledge of conditions and limitations in the facility license Knowledge ofless than or equal to one hour Tech Spec action statements for systerrts 3.0/3.6 3.9/4.3 2 68 69 4.5 4.5 2 96 97 3. Radiation Control Subtotal 2.3.5 2.3.12 2.3.11 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equij.J. ;;Ill, etc. Knowledge of radiological safety pertaining to licensed operator duties, such as containment entry, fuel handling, access to locked hiph-nuii:!tion areas, ali2nill!?

filters, etc. Ability to control radiation releases 2.9/2.9 3.2/3.7 70 71 4.3 2 98 Subtotal 2 1 4. Emergency Procedures/

Plan 2.4.4 2.4.19 2.4.20 2.4.47 i 2.4.6 2.4.23 Ability to l' i7P entry conditions for EOPs! AOPs Knowledge ofEOP layout, 1>J1I1Uo1::., and icons Knowledge of operational implications of EOP warnings, cautions, and notes. Ability to diagnose and recognize trends utilizing appropriate control room reference material Knowledge ofEOP mitigation strategies Knowledge ofthe bases for prioritizing emergency procedure imnlementation during "'l1J"'O"'l1"J Vlwuuw>

4.5/4.7 3.4/4.1 3.8/4.3 4.2/4.2 I I 72 73 74 75 4.7 4.4 99 100 Subtotal 4 2 II Tier 3 Point Total 10 7 ES-401 Record of Rejected F onn ES-40 1-4 Tier 2/1 211 2/1 2/1 l 3/1 3/2 III SRO 111 SRO 21l SRO Randomly Selected KJ A -061.K4.14 026.Al.04 078.K4.02 012.GEN.2.4.3 GEN.2.1.34 GEN.2.2.21 APE.022.GEN.2.4.21 WIE05.GEN.2.2.39 004.A2.09 Reason for Rejection N/A Millstone

3. No interlocks for Aux Feedwater Isolation at Millstone 3 Over-sample of monitoring/predicting Containment humidity.

Also selected in 022.A2.03 Over-sample of interlock for swap-over of service air to instrument air. Also selected in 079.A2.01 Generic KIA to identify post-accident instruments is NI A for the RPS system, which is used with the reactor trip breakers closed (pre-accident conditions)

Knowledge of primary/secondary chemistry limits. Rejection recommended by Ops Rep. Not conducive to discriminating RO level question Identity pre-post maintenance test requirements:

not part of RO job function Generic KIA to evaluate safety function is Nt A for loss of makeup AOP Over-sample of <1 hour Tech Specs for SRO. Also, NI A for loss of heat sink accident Over-sample of actions for high RCS activity.

Also selected in APE.076. A2.02 ES-401, Page 27 of33 i Administrative Topics Outline Form ES-30 1-1 , Facility:

Millstone Date of Examination:

7/11 -7/15/11 Examination Level: ROW SRoD Operating Test Number: 2K11 Administrative Topic Type Describe activity to be performed (see Note)

Code* Determine QPTR, Analyze Results and Make Recommendations.

Conduct of Operations KIA 2.1.19 (Ability to use plant computer to evaluate system RO A.1.1 component status) KIA Rating: 3.9/3.8 Perform a Shutdown Margin for MODE 3 with One Stuck Control Rod: Xe Correction Required.

Conduct of Operations M,R 2.1.37 (Knowledge of procedures, guidelines associated with RO A.1.2 reactivity management)

KiA Rating: 4.3/4.6 Perform a Manual RCS Leakage Calculation.

Equipment Control N,S KIA 2.2.12 (Knowledge of surveillance KiA Rating: Actions and Expected Response for RMS Equipment failure Alarms. Radiation KIA 2.3.5 (Ability to use radiation monitoring systems, such ROA.3 fixed radiation monitors .... ) KiA Rating: 2.9/2.9 Emergency Procedures I Plan Ie: *1\ E

• retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or (D)irect from bank ( .:::. 3 for ROs; .:::. 4 for SROs & RO (N)ew or {M)odified from bank ( (P)revious 2 exams ( < 1; randomly ES-301, Page 22 of 27 NUREG-1021, Rev 9, Supp 1 ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Millstone 3 Date of Examination:

7/11 -7/15/11 Examination Level: ROO SRO[i] Operating Test Number: 2K11 Administrative Topic Type Describe activity to be performed (see Note) Code* Administrative Requirements for Shift Manning Conduct of Operations M,R Activities

-Working Hour Limitations.

SRO A.1.1 KIA 2.1.5 (Ability to use procedures related to shift staffing .... ) KiA Rating: 2.9/3.9 Review a Surveillance for RCS Leakage, Analyze Conduct of Operations N,R Results and Take Appropriate Action. SRO A.1.2 KIA 2.1.7 (Ability to evaluate plant performance and make operational juclgements

.... ) KiA Rating: 4.4/4.7 Perform an Operability Determination.

Equipment Control N,R KIA 2.2.37 (Ability to determine operability and/or availability of SRO A.2 safety related equipment)

KiA Rating: 3.6/4.6 . Evaluation of an Unplanned Gaseous Release. Radiation Control N,R KIA 2.3.11 (Ability to control radiation releases)

KiA Rating: 3.8/4.3 SRO A.3 Emergency Plan Classification and Protective Action Recommendation for a General Emergency.

Emergency Procedures I Plan P,D,R KIA 2.4.41 12.4.44 (Knowledge of emergency action level SRO A.4 thresholds, classification

/ PARs) KiA Rating: 2.9/4.6 ; 2.4/4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom

{D)irect from bank for ROs; 4 for SROs & RO retakes) (N)ew or {M)odified from bank ( 1) (P)revious 2 exams ( <: 1; randomly selected)

ES-301, Page 22 of 27 NUREG-1021, Rev 9, Supp 1 Control Roomlln-Plant Systems Outline Form ES-301-2 Fac ility: Millstone Unit 3 Date of Examination:

7/11/11 Exa m Level: RO SRO-I D SRO-U D Operating Test No.: 2K11 Rev 2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. S.1 I Align Safety Grade Boration Path KIA Number: APE: 024 AA1.17; KIA Rating: 3.9/3.9 M, A, E, S 1 -004 b. S.2 / Respond to an Inadvertent Containment Isolation Phase 'A' KIA Number: 013 A4.02; KIA Rating: 4.3/4.4 N,E,EN,S 2 -013 c. S.3 I Perform an RCS Bleed and Feed per FR-H.1 KIA Number: EPE: EOS -EA1.1; KIA Rating: 4.1/4.0 D,A,E,S 3 -010 d. S.4 I Lineup RHR System in the Injection Mode (RCS Leak) KIA Number: EPE: 009 -EA 1.13; KIA Rating: 4.41 4.4 D,A, E,S,L 4.1 -005 e. S.5 I SGTR Cooldown Using Atmospheric Steam Relief or Bypass valves KIA Number: EPE: 038 -EA1.16; KIA Rating: 4.4/4.3 0, E,S 4.2-041 f. S.6 I Respond to High Containment Pressure KIA Number: EPE: E14-EA1.1; KIA Rating: 3.7/3.7 M, A, E, EN, S 5 -026 g. S.7 I Energize SBO Auxiliaries with the SBO Diesel KIA Number: 062 A1.01; KIA Rating: 3.4/3.8 N,E,S 6 -062 h. S.8 I Auxiliary Building South Floor Area Fire KIA Number: APE: 067 AA2.16; KIA 3.3/4.0 M,A,E,S 7 -012 In-Plant Systems@ (3 for RO); (3 for SRO-i); (3 or 2 for SRO-U) i. P.1 I Establish Service Water to Train "B" Control Building Chilled Water Cross Tie KIA Number: 076 K1.19; KIA Rating: 3.6/3.7 M, E 4.2 -076 j. P.2 / Primary PEO Actions on a Control Room Evacuation KIA Number: APE: 068 AA1.14; KIA Rating: 4.2/4.4 P,D,E,R 6 -062 k. P.3 / Spent Fuel Pool emergency Makeup 0, A, E, R 8 -033 KIA Number: 033 A2.03; KIA Rating: 3.1/3.S All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 14-6 I 2-3 (C)ontrol room (D)irect from bank <9/ (E)mergency or abnormal in-plant >1/ (EN}gineered safety feature -/-/ 1 (control room system) (L)ow-Power I Shutdown >11 (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams 3/ 3 I 2 (randomly selected) (R)CA >11 (S)imulator ES-301, Page 23 of 27 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Millstone Unit 3 Date of Examination:

7111/11 -Exam Level: RO D SRO-I LiJ SRO-U D Operating Test No.: 2K11 Rev 2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System 1 JPM Title Type Code* Safety Function S.1/ Align Safety Grade Boration Path M,A,E,S 1 -004 S.2 / Respond to an Inadvertent Containment Isolation Phase 'A' N,E,EN,S 2.-013 S.3 / Perform an RCS Bleed and Feed per FR-H.1 D,A,E,S 3 -010 SA / Lineup RHR System in the Injection Mode (RCS Leak) D,A,E,S,L 4.1 -005 S.61 Respond to High Containment Pressure M,A, EN, 5 -026 S S.7/ Energize SBO Auxiliaries with the SBO Diesel N,E,S 6 -062 S.8 / Auxiliary Building South Floor Area Fire M,A,E,S 7 -012 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 fOl' SRO-U) P.1 1 Establish Service Water to Train "B" Control Building Chilled M, E 4.2 -076 Water Cross Tie P.21 Primary PEO Actions on a Control Room Evacuation P,D,E,R 6 -062 P.31 Spent Fuel Pool emergency Makeup D A, E, R 8 -033 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Criteria for RO / SRO-II SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D}irect from bank :5.91 (E)mergency or abnormal in-plant >11 >1 (EN)gineered safety feature -I -I 1 (control room system) (L)ow-Power 1 Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams :5. 3 I 3 I :5. 2 (randomly selected) (R)CA (S)imulator ES-301, Page 23 of 27 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Millstone Unit 3 Date of Examination:

7/11/11 Exam Level: RO D SRO-I D SRO-U LiJ Operating Test No.: 2K11 Rev 2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System 1 JPM Title Type Code* Safety Function a. S.1 I Align Safety Grade Boration M,A,E,S 1 -004 b. SAl Lineup RHR System in the Injection Mode (RCS Leak) D,A,E,S,L 4.1 -005 S.6/ Respond to High Containment Pressure M,A, EN, 5 -026 S In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) d. P.1 / Establish Service Water to Train "B" Control Building Chilled M,E 4.2 -076 Water Cross Tie e. P.21 Primary PEO Actions on a Control Room Evacuation P,D,E,R 6 -062 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6 14-6 1 2-3 (C)ontrol room (D)irect from bank :5.91:5.8/:5.

4 (E)mergency or abnormal in-plant (EN)gineered safety feature -1 1 1 (control room system) (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) ?,.2/?,.2/?,.1 (P)revious 2 exams :5. 3 1 :5. 3 1 :5. 2 (randomly selected) (R)CA >1/?,.1 (S)imulator ES-301, Page 23 of 27 I Appendix 0 Scenario Outline Form ES-D-1 Facility:

Millstone 3 -Scenario No.: 2K11 NRC-01 Op-Test No.: 2K11 Examiners:

Operators:

Initial Conditions:

IC-18, 100% Power, Middle of life, Eguilibrium Xe.

The I2lant is at 100% 120wer and at the middle of life. The "Au TPCCW l2uml2 is out service for oil rel2lacement Event Malf. No Event No. Type* 1 2 RX10A I (RO) 3 I MS11A I (BOP) 4 FW01 R (RO) R (SRO) N (BOP) 5 ED04C C (RO) C (BOP) 6 RC02D M (ALL) 7 TC03 C (BOP) 8 S107A1B C (RO) 9 FW19 M (ALL) Event Description

'B' MD AFW pump oil leak. (Tech Spec entry) Controlling channel of PZR level fails just below setpoint. (AOP 3571) 'A' SG pressure channel failure. (3MSS-PT20A) (Annunciator response, AOP 3571) Loss of condenser vacuum and procedurally directed rapid down power (5%/min).

Vacuum will stabilize. (AOP 3559, AOP 3575) Loss of emergency bus 34C. (AOP 3577) Small break LOCA inside CTMT. Requires Trip and Safety Injectio,!. (AOP Turbine fails to trip automatically or manually, requires a turbine SIH pumps fail to Loss of Secondary Heat Sink. TD AFW pump trips, MD AFW pump deenergized due 'to loss of bus 'B' MD AFW pump in PTL due to no oil. (success will be to establish Main Feed) * (N)ormal, (R )eactivity, (I )nstrument, (C)omponent, (M)ajor AppendiX D, Page 38 of 39 8 Appendix 0 Scenario OutlinE! Form ES-D-1 Facility:

Millstone 3 Scenario No.: 2K11 NRC-02 Op-Test No.: 2K11 Examiners:

Operators:

Initial Conditions:

IC-18. 100% Power. Middle of life. Equilibrium Xe. Turnover:

The I2lant is at 100% 120wer and at middle of life. The "Alf EDG is out of service for I2lanned maintenance.

Event Malf. No. No 1 RX05D 2 RX12G 3 SG03B 4 MS01B 5 RP10AlB RP09B 6 RP08A1B 7 RP11E SG01B il * (N)ormal, Event Type* I (RO) I (BOP) R(RO) R (SRO) N (BOP) M (ALL) C (RO) C (BOP) C (RO) M (ALL) (R Event Loop 4 Tavg fails high (loop 4 narrow range (AOP 3571) 'C' steam generator level channel (controlling) fails low. (AOP 3571) * 'B' SG Tube Leak (AOP 3576), and subsequent procedurally required rapid downpower.

(3%/min). (AOP 3576, AOP 3575} 'B' main steam line break in CTMT. Requires Reactor Trip and Safety Injection.

Automatic and IVIB7 manual reactor trip switch fail. Successful manual reactor trie Mf?4. Main Steamline Isolation fails to automatically actuate. Several HPSI components fail to respond to a Safety Injection signal. Hot, dry '8' SG results in a SGTR. Faulted, ruptured SG. (I}nstrument, (C)omponent, (M)ajor Appendix 0, Page 38 of 39 I Appendix D Scenario Form ES-D-1 Facility:

Millstone 3 Scenario No.: 2K11 NRC-04 (sQare) Op-Test No.: 2K11 -

Opemtors:

Initial Conditions:

IC-OB (modified}, 7% 120wer, Beginning of Life, No Xe.

The crew will take the shift with reactor 120wer stable and just having entered MODE (reactor 120wer 7%), following a reactor startul2 by the I2revious shift. This is the Qlant startuQ from a refueling outage. OP 3203, Plant Startu{2 is in Event Malf. No. No 1 NI11 SW01C NI09B RC25B ED01 EG13A RP11M CV13B RC02B 8 RP07A1B 9 RP11L 10 RC02C RP06A1B * (N)ormal, Event Type* R R N C I C C C M C (RO) C (BOP) C (RO) (R )eactivity.

Power increase to place the Main Turbine online OP 3203, Plant Startup. (Section P-10 Permissive failure results in a termination of startup and Tech Spec 3.0.3 'C' Service Water Pump trip. (Annunciator Power Range Nuclear Instrument (NI) Channel Lower Detector fails high requiring FRV Bypass controllers to be placed in 'B' RCP high shaft vibration requiring an shutdown of the affected RCP. (Annunciator

• AOP 3554) Loss of offsite power. 'A' Emergency Diesel Generator (EDG) fails to automatically start and must be manually started from MB8. BOP must manually close the 'A' and 'B' EDG output breakers.

Small break LOCA inside CTMT (catastrophic loss of 'B' RCP seal package).

Safety Injection required.

Safety I njection fails to automatically Feedwater Isolation fails to automatically Large break LOCA inside CTMT. CDA fails to (I)nstrument. (C)omponent, (M)ajor Appendix D, Page of 39 i